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  1. 1
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    Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel

    Published 1999
    Government Document Microfilm Book

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  2. 2
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    Modification of IPSN's SCANAIR fuel rod transient code for high burnup VVER fuel

    Published 1999
    Government Document Microfilm Book

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  3. 3
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    Delayed hydride cracking of zirconium alloy fuel cladding.

    Published 2010
    Book

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  4. 4
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    Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding

    Published 2003
    Government Document Microfilm Book

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  5. 5
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    Predicted increase in fuel rod cladding oxidation

    Published 1998
    Online Access
    Online Access
    Government Document Electronic eBook

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  6. 6
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    Delayed hydride cracking of zirconium alloy fuel cladding

    Published 2010
    Online Access
    Electronic eBook

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  7. 7
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    A new comparative analysis of LWR fuel designs by O'Donnell, G. M.

    Published 2001
    Government Document Microfilm Book

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  8. 8
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    Self shielding in rectangular and cylindrical geometries / by Schneider, Harold

    Published 1956
    Government Document Book

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  9. 9
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    Cladding rupture, swelling & coolant blockage as a result of a reactor accident.

    Published 1979
    Online Access
    Government Document eBook

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  10. 10
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    Air oxidation kinetics for Zr-based alloys by Natesan, K. (Krishnamurti), 1942-

    Published 2004
    Government Document Microfilm Book

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  11. 11
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    Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding / by Shestopalov, A., Lioutov, K., Yegorova, L. A. (Larisa Alexandrovna)

    Published 2003
    Online Access
    Government Document eBook

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  12. 12
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    FRAPCON-3.4 integral assessment / by Geelhood, K. J.

    Published 2011
    Online Access
    Online Access
    Government Document Electronic eBook

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  13. 13
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    Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel / by Shestopalov, A.

    Published 1999
    Online Access
    Government Document eBook

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  14. 14
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    Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding procedures and results of low temperature biaxial burst tests and axial tensile tests /

    Published 2001
    Government Document Microfilm Book

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  15. 15
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    Zirconium in the nuclear industry : proceedings of the ... international conference /

    Published 1977
    Request a PDF (UCB only)
    Conference Proceeding

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  16. 16
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    Corrosion of research reactor aluminium clad spent fuel in water.

    Published 2003
    Click here to view publication online
    Book

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  17. 17
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    FRAPCON-3.4 a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup / by Geelhood, K. J.

    Published 2011
    Online Access
    Online Access
    Government Document Electronic eBook

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  18. 18
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    Assessment of current test methods for post-LOCA cladding behavior by Billone, Michael C.

    Published 2012
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    Online Access
    Government Document Electronic eBook

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  19. 19
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    Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / by Belaïd, S., Freixa, J., Zerkak, O.

    Published 2013
    Online Access
    Online Access
    Government Document eBook

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  20. 20
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    NUREG-0630 "Cladding, swelling and rupture--models for LOCA analysis".

    Published 1980
    Online Access
    Government Document eBook

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